Published December 1988
| Version v1
Journal article
Liquid-metal-cooled reactor thermal-hydraulic calculations in the United States
Description
A wide range of thermal-hydraulic computer codes has been developed by various organizations in the United States. These codes cover an extensive range of purposes from within-assembly-wise pin temperature calculations to plantwide transient analysis. The codes are used for static analysis, analysis of protected anticipated transients, and analysis of unprotected transients for the more recent liquid-metal-cooled reactor designs. Some of these codes are plant specific; others are more general and can be applied to a number of plants or designs
Additional details
Publishing Information
- Journal Title
- Nuclear Science and Engineering
- Journal Volume
- 100
- Journal Issue
- 4
- Series
- Nucl. Sci. Eng.
- Journal Page Range
- 558-563
- ISSN
- 0029-5639
- CODEN
- NSENA
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20057397
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTER CODES; LIQUID METAL COOLED REACTORS; NUCLEAR POWER PLANTS; SPECIFICATIONS; TRANSIENTS; USA
- Descriptors DEC
- DEVELOPED COUNTRIES; NORTH AMERICA; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; THERMAL POWER PLANTS